Skip to main content
SpringerLink
Log in

SCC of Alloy 152/52 Welds Defects, Repairs and Dilution Zones in PWR Water

  • Conference paper
  • First Online:
Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors

Part of the book series: The Minerals, Metals & Materials Series ((MMMS))

  • 3128 Accesses

Abstract

Extensive SCC growth rate measurements have been performed on Alloy 690 and its weld metals in the past, and this paper focuses on SCC growth rate evaluation of Alloy 52/152 welds with a variety of defects and/or weld repairs , and in the dilution zone. Ductility dip cracking dominated the weld defects , and weld repair mockups were fabricated by EPRI Charlotte to be 20% or 50% excavation and repair, as well as welds with a refuse pass every layer. Only low and very low SCC growth rates were observed in all cases. Studies on weld dilution zone effects of varying Cr content were evaluated using welds created with variable ratios of dual-filler-wire feel, which permits definitive SCC growth rate measurements in a homogenous weld without the ambiguity of having the crack front in undefined composition of an actual weld dilution zone.

This is a preview of subscription content, log in via an institution to check access.

Access this chapter

Log in via an institution
Chapter
USD 29.95
Price excludes VAT (USA)
  • Available as PDF
  • Read on any device
  • Instant download
  • Own it forever
eBook
USD 259.00
Price excludes VAT (USA)
  • Available as EPUB and PDF
  • Read on any device
  • Instant download
  • Own it forever
Hardcover Book
USD 329.99
Price excludes VAT (USA)
  • Durable hardcover edition
  • Dispatched in 3 to 5 business days
  • Free shipping worldwide - see info

Tax calculation will be finalised at checkout

Purchases are for personal use only

Institutional subscriptions

References

  1. P.L. Andresen, Perspective and direction of stress corrosion cracking in hot water, in Proceedings of 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems, NACE, 2001

    Google Scholar 

  2. P.L. Andresen, T.M. Angeliu, L.M. Young, Immunity, Thresholds, and Other SCC Fiction (TMS, Proc. Staehle Symp. on Chemistry and Electrochemistry of Corrosion and SCC, 2001)

    Google Scholar 

  3. P.L. Andresen, L.M. Young, P.W. Emigh, R.M. Horn, Stress corrosion crack growth rate behavior of Ni alloys 182 and 600 in high temperature water, corrosion/02, paper 02510, NACE, 2002

    Google Scholar 

  4. P.L. Andresen, Conceptual similarities and common predictive approaches for SCC in high temperature water systems, paper 96258, corrosion/96, NACE, 1996

    Google Scholar 

  5. F.P. Ford, P.L. Andresen, Corrosion in nuclear systems: environmentally assisted cracking in light water reactors, in Corrosion Mechanisms, ed. By P. Marcus and J. Ouder, Marcel Dekker, pp. 501–546, 1994

    Google Scholar 

  6. P.L. Andresen, C.L. Briant, Environmentally Assisted Cracking of Types 304L/316L/316NG Stainless Steel in 288 ℃ Water. Corrosion 45, 448–463 (1989)

    Article  CAS  Google Scholar 

  7. P.L. Andresen, Environmentally assisted growth rate response of nonsensitized AISI 316 grade stainless steels in high temperature water. Corrosion. 44 (7), 450 (1988)

    Article  CAS  Google Scholar 

  8. P.L. Andresen, J. Hickling, PWSCC growth rates of cold worked alloy 690, Conference on Alloy 600, Santa Ana Pueblo, NM, March 2005, EPRI, Palo Alto

    Google Scholar 

  9. P.L. Andresen, Development of advanced testing techniques to quantify the improved PWSCC resistance of alloy 690 and its weld metals (MRP-123), EPRI, Palo Alto, CA, 2004. Technical report 1010269

    Google Scholar 

  10. P.L. Andresen, M.M. Morra, Materials reliability program: Resistance of alloy 690/52/152 to SCC crack growth in simulated PWR Primary Water (MRP-196), EPRI, Palo Alto, CA, 2006, Technical report 1013516

    Google Scholar 

  11. P.L. Andresen, M.M. Morra, K. Ahluwalia, Effect of deformation temperature, orientation and carbides on SCC of alloy 690, in Proceedings of 16th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, NACE, Aug 2013

    Google Scholar 

  12. P.L. Andresen, M.M. Morra, K. Ahluwalia, SCC of alloy 152/52/52i weld metals in PWR primary water, in Proceedings of 16th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, NACE, Aug 2013

    Google Scholar 

  13. P.L. Andresen, Overview and Perspective on Stress Corrosion Cracking of Alloy 690 and Alloy 152/52 Weld Metals, Report 3002009966 (EPRI, Palo Alto, 2017)

    Google Scholar 

  14. P.L. Andresen, M.M. Morra, K. Ahluwalia, SCC of alloy 690 and its weld metals, in Proceedings of 15th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, The Metallurgical Society, Aug 2011

    Chapter  Google Scholar 

  15. P.L. Andresen, M.M. Morra, K.S. Ahluwalia, J. Wilson, Effect of deformation and orientation on SCC of Alloy 690, in Proceedings of 14th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, American Nuclear Society, Aug 2009

    Google Scholar 

  16. P.L. Andresen, M. M. Morra, J. Hickling, K.S. Ahluwalia, J.A. Wilson, PWSCC of alloys 690, 52 and 152, in Proceedings of 13th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, Canadian Nuclear Society, Aug 2007

    Google Scholar 

  17. P.L. Andresen, The Present and Future of SCC Testing of Alloy 690 and Its Weld Metals, Alloy 690 Experts Meeting (EPRI, Tampa, 2009)

    Google Scholar 

  18. P.L. Andresen, SCC of Alloy 690 Base Metal and HAZ in PWR Primary Water and of Alloy 52 & 152 Weld Metals in PWR Primary Water, Alloy 690 Experts Mtg (EPRI, Tampa, 2010)

    Google Scholar 

  19. M.B. Toloczko, S.M. Bruemmer, Crack Growth Response of alloy 690 in simulated PWR Primary Water, in Proceedings of 14th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, American Nuclear Society, Aug 2009

    Google Scholar 

  20. M.B. Toloczko, M.J. Olszta, N.J. Overman, S.M. Bruemmer, observations and implications of intergranular stress corrosion crack growth of alloy 152 weld metals in simulated PWR primary water, in Proceedings of 16th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, NACE, Aug 2013

    Google Scholar 

  21. S.M. Bruemmer, M. Olszta, M.B. Toloczko, Microstructural effects on stress corrosion crack growth in cold-worked alloy 690 tubing and plate materials, in Proceedings 16th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, NACE, Aug 2013

    Google Scholar 

  22. M.B. Toloczko, M.J. Olszta, S.M. Bruemmer, 1D cold rolling effects on SCC growth in alloy 690 tubing and plate materials and SCC crack growth testing of alloy 52 M in simulated PWR Primary Water, in Proceedings of 15th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, The Metallurgical Society, Aug 2011

    Google Scholar 

  23. D.J. Paraventi, W.C. Moshier, Alloy 690 SCC growth rate testing, in Workshop on Cold Work in Iron- and Nickel-Base Alloys, ed. by R.W. Staehle, J. Gorman, June 2007, EPRI, Palo Alto

    Google Scholar 

  24. D.J. Paraventi, W.C. Moshier, Alloy 690 SCC growth rate testing, in Proceedings of EPRI Alloy 690 Workshop, Atlanta, 31 Oct 2007

    Google Scholar 

  25. B. Alexandreanu, O. K. Chopra, W.J. Shack, The stress corrosion cracking behavior of alloys 690 and 152 weld in a PWR environment, PVP2008-61137, in Proceedings of ASME PVP, 2008

    Google Scholar 

  26. B. Alexandreanu, The stress corrosion cracking behavior of alloys 690 and 152 weld in a PWR environment, in Proceesings of 14th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, American Nuclear Society, Aug 2009

    Google Scholar 

  27. D. Tice, Personal communication on crack growth rate of alloy 690, AMEC (Serco), April 2010

    Google Scholar 

  28. D. Tice, S. Medway, N. Platts, J. Stairmand, I. Armson, Crack growth testing of cold worked alloy 690 in primary water environment, in Proceedings of 15th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, The Metallurgical Society, Aug 2011

    Google Scholar 

  29. D. Gomez-Briceno et al., “CGR testing of alloy 690 and weld metals 52 and 152”, alloy 690 experts meeting (EPRI, Tampa, 2010)

    Google Scholar 

  30. A.R. Jenks, G.A. White, P. Crooker, Assessment of laboratory PWSCC crack growth rate data for Nickel-based alloys, in International Light Water Reactor Materials Reliability Conference and Exhibition 2016, 1–4 Aug 2016, EPRI, Palo Alto, 2016. (and final EPRI report, in press)

    Google Scholar 

  31. ASME boiler and pressure vessel code, Sections III and XI, ASME, NY

    Google Scholar 

  32. M.J. Esmacher, SCC of industrial utilities: Boiler and cooling water systems, in Stress Corrosion Cracking: Mechanisms, Materials and Application to Industrial Problems, eds. by V.S. Raja, T. Shoji, Woodhead Publishing, 2010

    Google Scholar 

  33. P.L. Andresen, P.W. Emigh, M.M. Morra, R.M. Horn, Effects of yield strength, corrosion potential, stress intensity factor, silicon and grain boundary character on the SCC of stainless steels, in Proceedings of 11th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, ANS, 2003

    Google Scholar 

  34. P.L. Andresen, M.M. Morra, SCC of stainless steels and Ni alloys in high temperature water. Corrosion 64, 15–29 (2008)

    Article  CAS  Google Scholar 

  35. P.L. Andresen, G.S. Was, SCC of unirradiated stainless steels and Nickel alloys in hot water, in 17th International Corrosion Congress, Las Vegas, NACE, Houston, 2008

    Google Scholar 

  36. M.M. Morra, M. Othon, E. Willis, S. McCracken, “Characterization of Structures and Strains in 52-type and 152 Welds”, Alloy 690/52/152 PWSCC Research Collaboration Meeting (Tampa, Florida, 2011)

    Google Scholar 

  37. T.M. Angeliu, P.L. Andresen, J.A. Sutliff and R.M. Horn, intergranular stress corrosion cracking of unsensitized stainless steels in BWR Environments, in Proceedings of 9th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, AIME, 1999

    Google Scholar 

  38. T.M. Angeliu, P.L. Andresen, E. Hall, J.A. Sutliff, S. Sitzman, Strain and microstructure characterization of austenitic SS weld HAZs”, Corrosion/2000, Paper 00186, NACE, 2000

    Google Scholar 

  39. J.A. Sutliff, An investigation of plastic strain in copper by automated-EBSP, Microsc. Microanal. 5(Supp. 2), 236 (Proc: Microscopy & Microanalysis ‘99) (1999)

    Google Scholar 

  40. M.A. Othon, M.M. Morra, EBSD characterization of the deformation behavior of alloy 182 weld metal, Microscopy and Microanalysis, 11(Suppl 2), 522–523CD Cambridge University Press, (2005). doi:https://doi.org/10.1017/S1431927605506949

  41. G.A. Young, M.J. Hackett, J.D. Tucker, T.E. Capobianco, Welds for Nuclear Systems, Comprehensive Treatise on Materials for Nuclear Systems, ed. by R. Konings, Editor in Chief (Elsevier Science, to be published in 2011)

    Google Scholar 

  42. P.L. Andresen, C.L. Briant, Role of S, P and N segregation on intergranular environmental cracking of stainless steels in high temperature water, in Proceedings of 3rd International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, AIME, pp. 371–382, 1988

    Google Scholar 

  43. P.L. Andresen, The Effects of Aqueous Impurities on Intergranular Stress Corrosion Cracking of Sensitized Type 304 Stainless Steel, Final Report NP3384 Contract T115-3 (EPRI, 1983)

    Google Scholar 

  44. P.L. Andresen, J. Hickling, K.S. Ahluwalia, J.A. Wilson, Effects of hydrogen on SCC growth rate of Ni alloys in high temperature water. Corrosion 64(9), 707 (2008)

    Article  CAS  Google Scholar 

  45. P.L. Andresen, J. Hickling, K.S. Ahluwalia, J.A. Wilson, effects of PWR Primary Water Chemistry on PWSCC of Ni alloys, in Proceedings of 13th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, Canadian Nuclear Society, Aug 2007

    Google Scholar 

  46. S.A. Attanasio, D.S. Morton, Measurement of the Ni/NiO transition in Ni–Cr–Fe alloys and updated data and correlation to quantify the effect of aqueous hydrogen on primary water SCC, in Proceedings 11th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems, ANS, 2003

    Google Scholar 

  47. L.W. Niedrach, A new membrane type pH sensor for use in high temperature high pressure water. J. Electrochem. Soc. 127, 2122 (1980)

    Article  CAS  Google Scholar 

  48. Elaine West, D.S. Morton, John Mullen, Bob Etien and Heather Mohr, SCC behavior of EN52/EN52i in deaerated water, in Proceedings of 16th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, NACE, Aug 2013

    Google Scholar 

  49. BWR vessel and internals project, evaluation of crack growth in BWR stainless steel RPV internals (BWRVIP-14-A), EPRI Report TR-105873, Mar 1996

    Google Scholar 

  50. S.M. Bruemmer, Unpublished data (Pacific Northwest Nat, Lab, 2016)

    Google Scholar 

  51. G. White, Crack Growth Rates for Evaluating Primary Water Stress Corrosion Cracking (PWSCC) of thick-wall alloy 600 materials, MRP-55 Revision 1, Final Report 1006695, EPRI (Palo Alto, CA, 2002)

    Google Scholar 

  52. Crack Growth Rates for Evaluating Primary Water Stress Corrosion Cracking (PWSCC) of Alloy 82, 182, and 132 Welds (MRP-115), EPRI Final Report 1006696, Nov 2004

    Google Scholar 

  53. P.L. Andresen, SCC of high Cr alloys in BWR environments, in Proceedings of 15th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, The Metallurgical Society, Aug 2011

    Chapter  Google Scholar 

Download references

Author information

Authors and Affiliations

  1. Andresen Cons., 12204 Wildwood Park Pl, Bakersfield, CA, 93311, USA

    Peter L. Andresen

  2. GE Research, One Research Circle CE 2545, Schenectady, NY, 12309, USA

    Martin M. Morra

  3. EPRI, 3420 Hillview Ave, Palo Alto, CA, 94304, USA

    Kawaljit Ahluwalia

Authors
  1. Peter L. Andresen
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. Martin M. Morra
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. Kawaljit Ahluwalia
    View author publications

    You can also search for this author in PubMed Google Scholar

Corresponding author

Correspondence to Peter L. Andresen .

Editor information

Editors and Affiliations

  1. Idaho National Laboratory, Idaho Falls, ID, USA

    John H. Jackson

  2. Naval Nuclear Laboratory, Pittsburgh, PA, USA

    Denise Paraventi

  3. Chalk River Laboratories, Canadian Nuclear Laboratories, Chalk River, ON, Canada

    Michael Wright

Rights and permissions

Reprints and permissions

Copyright information

© 2019 The Minerals, Metals & Materials Society

About this paper

Cite this paper

Andresen, P.L., Morra, M.M., Ahluwalia, K. (2019). SCC of Alloy 152/52 Welds Defects, Repairs and Dilution Zones in PWR Water. In: Jackson, J., Paraventi, D., Wright, M. (eds) Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The Minerals, Metals & Materials Series. Springer, Cham. https://doi.org/10.1007/978-3-030-04639-2_3

Download citation

Publish with us

Policies and ethics

Search

Navigation